ML20094A084

Rev 0 to TMI-1,Post-Accident RMA-5 Grab Sampling & MAP-5 Filter Removal Radiological Analyses

ML20094A084
Person / Time
Site:	Three Mile Island
Issue date:	07/02/1984
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20094A069	List: ML20094A082 ML20094A084
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM TDR-563, NUDOCS 8408030108
Download: ML20094A084 (26)

Text

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g {g TDR NO. 5^3 _ REVISK)N NO. __0___ __

EUDGET TECHlitCAL DATA REPORT ACTivlTY NO. 412013 PAGE CF _

PftOJECT:

T DEPARTMENTiGECTION 7 - -:MI.. FUEL PROJECIS/,7

- m7.;--- ,_

RELEASE DATE __ REVISION DATE _.

DOCUMENT TITLE: WI-1; POST ACCIDENT EMA-5 GRAB SAMPLING AND MAP-5 IILTER REMOVAL RADIOLOGICAL ANALYSES

ORIGINATOR SIGNATURE DATE APPROVALISI SIGNATURE DATE 4.und;f#X~ MVM ,AEW *m APPROVAL FOR EXTERNAL DISTRIBUTION DATE d 7-2.f4 Does this TDRInclude recommendation (s)? Oyes DNo if yes,TFWR/TR *-

o DICTRIBUTION ABSTRACT:

This report esticates the TMI-en-site radiological conditions in terms of personnel radiation exposure during the post T. . ghton acc & nt cond M on for both grab samp u ng and W M ter T. Y. By sampling in the off-gas stream.

0 D. K. Croneberger l

RESULTS AND CONCLUSION l J. P. Donnachie ( EI) f'g* " #( I) g The radiation exposure to personnel during sampling M. R. Knight ( E I) activities are:

I J. V. Lengenbach WHOLE BODY EXTREMITY

. .' . $h teh ( ) (E )

"" ( I) l f [* . USING MARINNELI 1.3(-1) 9.9(-2)

J.D$Sn B AKER TO CARRY ,

J. A. Tangen N08LE GAS THE SAMPLE '

gggpg73g

( I)

S' f h . USING 25 cc BULB TO CARRY M 9.3(-2) 8.5(-3)

J. Wetmore R. F. Wilson 3 MAP-5 FILTER 1.1 6.0 REW) VAL NUREG-0737 5 75 LIMITS These results demonstrate that the integrated dose for each I

activity, during Post Accident condition, is in coepliance with NUREG-0737 limits. -

8408030108 840730 PDR ADOCK 05000289 G PDR ~~

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TDR 563 Page 2 of 26 TABLE OF CONTENTS

1.0 INTRODUCTION

4 2.0 METHODS 4 2.1 Dose Acceptance Criteria 4 2.2 Exposure Analysis for Obtaining Noble Gas Sample at RMA-5 5 2.2.1 Source Ters 5

2.2.2 Sampling Activity Scenario 5 l

2.2.3 Radioactive Exposure to the Personnel During RMA-5 Grab Sampling Activities 6 f 2.2.3.1 Dose Rate Due to Piping of t'.e

Sampling Panel 6 2.2.3.2 Dose Rate Due to Marinelli Beaker 9

2.2.3.3 Dose Rate Due to the 25cc Bulb 9

, 2.2.4 Radiation Exposure During Sample Analysis 10 2.2.5 Dose Received by Personnel During Post 11 Accident RMA-5 Grab Sample Activitie:3

2.3 Exposure Analysis for Obtaining the MAP-5 (at RMA-5) Filters 15 l

2.3.1 Source Term 15 2.3.2 Filter Removcl Activity Scenario 15 I 2.3.3 Radioactive Exposure to the Personnel During l MAP-5 Filter Removal 17 2.3.3.1 Dose Rate Due to Piping of the MAP-5 Sample Panel 18 2.3.3.2 Dose Rate Due to the MAP-5 Filters 21 2.3.4 Radiation Ex)osure During Sample Analysis 21 2.3.5 Radioactive ixposure to the Personnel During Post Accident MAP-5 Filter Removal Activities 22 l 2.4 Radioactive Exposure to the Personnel during Post Accident MAP-5 (at RMA-8 and RMA-9) Filter Removal Activities 22 2.5 Exposure Rate Connon for RMA-5 Grab Sampling and MAP-5 Filter Removal Activities 24 2.5.1 Dose Rate Due to the Airborne from the Containment 24 2.5.2 Dose Rate Due to the Containment Direct Shine 24 3.0

SUMMARY

OF RESULTS 25 s

4.0 REFERENCES

26

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TDR 563 Page 3 of 25 l LIST OF TABLES

1. Noble Gas and Iodine Concentration Normalized to 100Xf/cc 7

2. Time Taken for RMA-5 Grab Sampling Activities With and Without Breathing Apparatus 8

. 3. Dose Rate Due to Sample Panel Piping 12

4. Dose Rate Due to the Marinneli Beaker 12

5. Dose Rate Due to the 25cc 3ulb 12

6. A. Rad. Exposure using Marinneli Beaker to carry the sartple. 13 B. Rad. Exposure using 25cc Bulb to carry the sample. 14 l 7. Radiotodine Concentration Nornalized to 100 uc/cc 16 i

8. Tirpe Taken for MAP-5 Filter Removal Activities With j and Without Breathing Apparatus 19 1

9. Dose Rate Due to the MAP-5 Piping 20

10. Dose Rate Due to the MAP-5 Filters 20

11. Rad Exposure for MAP-5 Filter Removal 23 l f'

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TDR 563 l

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1.0 INTRODUCTION

The purpose of this TDR is to estimate radiation exposures under post l accident conditions for: 1) obtaining a noble gas sample at RMA-5; i and 2) collecting and analyzing MAP-5 filters. Based on time-and-motion data during the post accident condition, the exposure

, for compliance with the radiation criteria set by NUREG-0737, II B.3

[

is evaluated.

The radiation source terms in this report are those as stipulated in NUREG-0737. Radiation dose rates are analyzed by using the computer codeISOSHLDII(Ref.1),whichemploysapointkernelintegration  :

method.

2.0 METHODS ,

2.1 Dose Acceptance Criteria Criterion of GDC19, Appendix A, 10CFR Part 50 requires that radiation protection be provided such that the dose to personnel should not be in excess of:

I 5 rem Whole Body 75 rem Extremities s

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TDR 563

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Page 5 of 26 2.2 Exposure Analysis for Obtaining Noble Gas Sar.ple at RMA-5 e

r L 2.2.1 Source Ters 1

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The source term from RMA-5 was assumed to be 100 uci/cc.

i This assumption was based on the design basis maximum range for capability to detect and measure concentrations of noble gas in plant gaseous effluent during and following an accident, given in Table II.F.1-1 of NUREG-0737 (Ref. 2).

For isotopic distribution, 100% noble gas and 55 iodine

~

core inventory for 310 effective full power days were normalized to 100 uci/cc. Yhe normalized source term are presented in Table 1.

) 2.2.2 Sampling Activity Scenario The time and motion study for the post accident RHA-5 grab sampling was conducted by the plant Radiological Engineering. This study was based on the use of no I protective breathing apparatus. In this report, we have I assumed a 255 increase in the motion time to account for the slowdown due to the wearing the breathing apparatus.

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TDR 563 Page 6 of 26 The time and motion data of the technician moving from the radiochemistry lab to the grab sample panel and back to the lab for both with and without protective breathing

! apparatus are shown in Table 2.

i 2.2.3 Radioactive Exposure to the Personnel During RMA-5 Grab ,

Sempling Activities In order to account for the radioactive exposure to the personnel while conducting the post accident RMA-5 grab sampling, two cases were considered: (1) using a marinneli beaker to carry the sample; and (2) using the 25 cc bulb.

2.2.3.1 Dose Rate Due to Piping of the Sample Panel The piping that carry the RMA-5 gas sample consist of: (1) the piping that runs under the floor panel beneath the sample panel; (2) the piping that runs along the sample panel. ine outside diameter of these piping is either 1/2 or 1/4 inch. The analysis conservatively assumed that the entire radius of the piping is filled with source term shown in Table 1, with l no credit for piping wall thickness shielding.

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TDR 563

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Page 7 of 26 TABLE 1 NOBLE GAS AND IODINE CONCENTRATION NORMALIZED TO 100uci/cc Normalized to 100 uC1/cc As Per NUREG-0737 .

Isotope (uCi/cc)

BR-84 l 1.685 + 0 XR-83m 1.990 + 0

-85m 4.709 + 0

-85 1.137 - 1

-87 8.599 + 0

-88 1.207 + 1 Xe-131m 9.431 - 2

-133m 6.595 - 1

-133 2.725 + 1

-135m 7.004 + 0

-135 4.494 + 0

-138 2.517 + 1

. I-131 7.906 - 1

-132 9.293 - 1

-133 1.373 + 0

-134 1.720 + 0

-135 1.365 + 0 Total 100

TLR 563 Page 8 of 26 TABLE 2 TIME TAKEN FOR RMA-5 GRAB SAMPLING ACTIVITIES WITH AND WITHOUT BREATHING APPARATUS I

Time Without Time With Activity Breathing Apparatus Breathing Apparatus Transit time from Lab to grab sampling panel 1.5 min 2 min Draw RMA-5 air sample to marinelli breaker 8 min 10 min Draw RMA-5 air sample to 25cc bulb 2 min 3 min Transit time from grab sample panel to lab 1.5 min 2 min I

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TCR 563 Page 9 of 26 The dose rate, at different distances, due to sample panel piping and the piping beneath the sample panel are shown in Table 3.

2.2.3.2 Dose Rate Due to Marinneli Beaker The marinnelt beaker is a 1640 cc container which may be used to carry the noble ga sample from the sample panel to the radiochemistry lab. Dose rates due to the marinneli beaker when filled with sample gas, at different distances from the marinnelt beaker surface are computed and presented in Table 4.

2.2.3.3 Dose Rate Due to the 25 cc Bulb Instead of the marinneli beaker, a 25 cc bulb may be used to carry the noble gas sample from the sanple panel to the lab. The bulb is a 25 cc container. Dose rates due to the 25 cc bulb, when filled with sample gas, at different distances from the bulb's surface are computed and presented in Table 5.

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TDR 563 Page 10 of 26 I'

2.2.4 Radiation Exposure During Sample Analysis The RMA-5 grab sample analysis is performed by removing the sample carrier (marinneli beaker of 25 cc bulb) from the bag, ? lacing it in the Geli detector, and a sample q count rate is taken. Then the sample carrier is removed from the detector. The total exposure during this time will be approximate 1 7.84 x 10-2 whole body if the marinnelf beaker is used and 6.85 x 10-2 whole body if

the 25 cc bulb is used (Ref. 4). Details of these

/

i results are given below. Note that these values are based on assumption that the sample carrier is removed from the bag and placed in the detector with use of tongs.

Stay time Radiation Source

and work and Dose Rate Exposure Contribution description (rerit/hr) (rem) 20 min. to o Airborne frcm 6.84(-2) take for the containment i sample rate = 2.C (-1) count o Containment

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direct shine

= 5.0 (-3) .

r i 1 min to o Marinneli 1.01 (-?)

place and beaker remove the (at 1 ft) sample in = 6.08 (-2) the detector o 25 cc buio 2.03 (-4) r (at 1 ft.)

( = 1.22 (-2).

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• TDR 563 1:

- Page 11 of 26 2.2.5 Dose Received by Personnel During Post Accident RM-5 5

j Grab Sample Activities I

)

All the actions and motions by the personnel during the post accident RMA-5 grab sample activii.ies are accounted for. The exposure for both whole body and extremities due each source are presented in Table 6. Note that the '

total exposure shown in Table 6a represent the exposure due to use of marinneli beaker. Table 6b represents the exposure rate due to use of 25 cc bulb for carrying the E

sample gas. Further, it is assumed that the technician carries the marinneli beaker or 25 cc from sample panel f

to lab, containing RMA-5 sample, in a bag one foot away f

from his body.

The integrated whol,s body and extremity doses during the

[ post accident RMA-5 grab sampling activities are

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I 1.3 x iT rest and 9.9 x 10-2 rem respectively if the i marinneli Taker is used to carry the sample. These E values are 9.3 x 10-2 rem whole body and 8.5 x 10-3 rem extremity if the 25 cc beaker is used to carry the

sample, ,

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TDR 563 Page 12 of 26

. TABLE 3 DOSE RATE DUE TO SAMPLE PANEL PIPING (rem /hr)

Distance i ft. 2 ft. 3 ft. 5 ft. 10 ft.

Panel Piping 7.80-2 2.69-2 1.29-2 4.88-3 1.27-3 Piping Beneath the Panel . 6.41-3 2.05-3 9.50-4 3.52-4 9.06-5 TABLE 4 DOSE RATE DUE TO THE MARINNELI BEAXER (rem /hr)

Contact 1 ft. 2 ft. 3 ft. 5 ft. 10 ft.

1.78+1 6.08-1 1.77-1 7.90-2 2.94-2 7.63-3 TABLE 5 DOSE RATE DUE TO THE 25 CC BULB (rem /hr)

Contact 1 ft. 2 ft. 3 ft. 5 ft. 10 ft.

1.53 1.22-2 3.17-3 1.4$-3 5.41-4 1.36-4 i

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h b l i~ TABLE 6As RAD. EXPOSUPE USIPC MARithCLI BEAXER TO CARRY THE SAMPLE Red Exposure Radiation Level Ouring Work (ree/hr) (ree)

Daecription Stay Time Radiation Source 20 (-1) 6.8 (-3)

Trenoit from lab 2 min . Airborne from ccotsineent

. Containment direct ohine 5.0 (-3) (W.B.)

to greb-eesple panel 2.0 (-1) 10 ein . Airborne from containment

. Containment direct ehine 5.0 (-3) f 7 63 (-3) 3.6(-2)

Drew RNA-5 Air . Marinnell Seeker (W.B.)

. Underneath Piping 5.44 (-4)

Sample to Marinelli 9 min. & 1.27 (-3)

Booker 40 sec. . Penel Piping (10 ft.

sway from L penol) 6.08 (-1) 20 eec. . Marinneli Booker

) . Underneath Piping 3 26 (-2)

E (1 ft. 7.83 (-2)

- away froe . Penel piping panel)

C 1.73 (+1) 9.9 (-2) 2 20 sec. . Marinneli Beeker (extreelty)

- (Contact)

. J.i; W;im from Containment 2.0 (-1) h Transfer Marinneli 2 .i 5.0 (-3) 7.9 (-3) 2 Seeker to Lab. . Conteirament Direct Shine

. Marinneli Bsn'"r (at I ft.) 3.3 (-2) (W.E.)

7.B4 (-2)

Semple Analysie 20 min. . See Section 2.3.4 (W.8.)

( 1.3 (-1) W.B.

Total Dose

[ For the Teek 9.9 (-2) Extremity

[' (ree)

B k

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3  %

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TDR M3 Pepe 14 of 26 TABLE 68: RAD. EXPOSURE USING 25 CC BUL8 70 CARRY THE SAMPLE Red Expcaurt Radiation Level During Work Description Stay flJoe Radiation Source (ree/hr) (ree)

Transit from lab 2 min . Airborne froe containment 2.0 (-1) 6.8 (-3) to greb sample . Containment direct shine 5.0 (-3) (W.B.)

panel 3 min . Airborne from containment 2.0 (-1)

. Containment direct shine 5.0 (-3)

Drew PJM-5 Air . 25 cc bulb 1.M (-4) 1.03 (-2)

Sample to 25 cc bulb 2 ein. & . Lhdernoeth Piping 5.44 (-4) (W.B.)

40 sec . Penel Piping 1.27 (-3)

(10 ft.

evey rree panel) 20 sec. . 25 cc Bulb 1.22 (-2)

(1 ft. . thderneath Piping 3.26 (-2) away from . Panel piping 7.80 (-2) panel) 20 sec. . 25 cc Bulb 1.53 ( 0) 8.5 (-3)

(Contact) (extremity)

Trenefer 25 ce bulb 2 ein. . Airborne from Containment 2.0 (-1)

Beaker to Lab. . Containment Direct Shine 5.0 (-3) 7.24 (-3)

. 25 cc Bulb (at 1 ft.) 1.22 (-2) (W.B.)

Sascle Analysis 20 min. . See Section 2.3.4 6.54 (-2)

(W.B.)

Total Dose 9.3 (-2) W.8.

For the Task 8.5 (-3) Extremity (ree) l l

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TDR 563 Page 15 of 26 2.3 Exposure Analysis for Obtaining the MAP-5 (at RKA-5) Filters 2.3.1 Source Term The source term for MAP-5 filter was based 100 uci/cc of radioiodine concentration in the gaseous flow stipulated in Table II F.1-2 of NUREG-0737 (Ref. 2).

For radiofodine distribution, the iodine core inventory for 310 effective full power days were normalized to 100 uct/cc. The normalized source term are presented in Table 7. Flow rate of 3000 cc/ min (Ref. 3) for 3 min flow is used. All the radiofodine in the stream is assumed to be deposited on the MAP-5 filters. The integrated activity of radiciodines deposited on the filter at 3000 cc/ min for 3 min. collection time are shown in Table 7. In this study the MAP-5 filters are treated as point source.

2.3.2 Filter Removal Activity Scenario The time and motion study for the post accident MAP-5 filter removal was conducted by the plant Radiological I

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p TDR 563 Page 16 of 26 TABLE 7 RADI0 IODINE CONCENTRATION NORMALIZED TO 100 uci/cc Normalized to 100 uci/cc Total Activity As Per NUREG-0737 Co11ected in Filter Isotope uCf/cc for 3 min (Ci)

I-131 12.7 1.15-1 1-132 15.0 1.35-1 .

1-133 22.6 2.01-1 1-134 27.7 2.50-1 I-135 22.0 1.99-1 Totai 100 9.0-1 f

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? TDR 563 g Page 17 of 26 h '

. Engineering. This study was based on use of no P'

p protective breathing apparatus. A 25% time increaie added to the motion time to account for the breathing i

? apparatus.

E g The time acid motion data for the technician moving from the lab to the MAP-5 panel and back to the lab for both E

y with and without protective breathing apparatus are shown i in Table 8.

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2.3.3 Radioactive Exposure to the Personnel During MAP-5 Filter j Removat k

k c KW-5 sample panel has three cartridge holders, each

connected to a channel which transfer gaseous air from

. RMA-5 to MAP-5 filters in the cartridge holders for f

sampling. The flow rate through each channel is 3000 cc/ min. During the 30 min sampling period, the

[ normal settings are: channel 1, continuous sample; l

channel 2, 4 sec. sample, 36 sec. purge; channel 3, f 4 sec. sample, 396 sec. purge (Ref. 3).

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TDR 563 Page 18 of 26 Cartridge Not 1 is enclosed in a one inch lead shteiding and cartridges No. 2 and 3 are each enclosed in cartridge holders approximately 0.5 cm, shielding. During high level activity concentrationin the stream, the No. 1 cartridge filter is bypassed. In this report the dose contributions due to the cartridges No. 2 and 3 are considered. According to the plant radiological engineering staff (Ref. 4), in case of a low level 2

activity concentration in the flow, the filter cartridge is placed manually in cartridge holder No. 1.

2.3.3.1 Dose Rate Due to Piping of the MAP-5 Sample Panel l The piping that carry the sample air to MAP-5 cartridges have an outside diameter of 1/4 inch. In the analysis we have assumed that the entire radius of piping is filled with sample air with no credit taken for piping wall l

thickness shielding. The source term in MM-5 l piping are the same as those shown in Table 1.

I The dose rate, at different distances, due to the MAP-5 sample panel piping are shown in Table 9.

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' TOR 563 Page 19 of 26 TABLE 8 TIME TAKEN FOR MAP-5 FILTER REMOVAL ACTIVITIES' WITH AND WITH0tfT BREATHING APPARATUS Time Without Time With Activity Breathing Apparatus Breathing Apparatus Transit time from lab to MAP-5 panel 1.5 min 2 min Time at MAP-5 panel

• 4 min & 4 min & l (including time handling 30 sec 30 sec I holder)

Additional time in

• 6 min- 6 min general area '

Transit time from 1 min & 2 min &

{ MAP-5 panel to lab 45 sec 15 sec I

25% time increase for the breathing apparatus is not added for this activity.

- TDR 563 Page 20 of 26

, TABLE 9 DOSE RATE DUE TO THE MAP-5 PIPING (rem /hr) ,

Distance i ft. 2 ft. 3 ft. 5 ft. 10 ft.

6.41-2 2.05-2 9.50-3 3.52-3 9.06-5 TABLE 10 DOSE RATE DUE TO THE MAP-S FILTERS (rem /hr)

Distance Contact 1 f t ._ 2 ft. 3 ft. 5 ft. 10 ft.

Cartridge No. 2 '

3 min collection 6.59+2 6.54+0 1.91+0 8.81-1 3.37-1 8.90-1 Cartridge No. 3 0.3 nin collection 6.59+1 6.54-1 1.91-1 8.81-2 3.37-2 8.90-2 s

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TDR 563 Page 21 of 26 2.3.3.2 Dose Rate Due to the BP-5 Filters As already mentioned in this report the dose j contributiondue to cartridges No. 2 and 3 are considered. Cartridge No. 2, connected to channel No. 2, obtains 3 min. sample over a period of 30 min.; and cartridge No. 3, 0.3 min.'

out of 30 min. The flow through each channel is 3000 cc/ min. The cartridges are treated as point source and the dose rate due to each cartridge at different distances from the surface of cartridge holder are shown in Table 10. No shielding credit for the thickness of the cartridge holder is taken.

2.2.4 Radiation Exposure During Sample Analysis

The MAP-5 grab sample analysis is performed by removing the sample filter from the bsg placing it in the Geli detector, and a sample count rate is taken. Then the sample filter is removed from the detector (Ref. 4). The

total exposure during this time will be approximate 1 1.88

x 10'I whole body. Details of these results are given below. These values are based on assurption that the sample filters are is removed from the bag and placed in the detector with use of tongs.

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, TDR 563 Page 22 cf 26 Stey ti:se Radiation Source and work and Dose Rate Exposure Contribution description (rem /hr) (res) 20 min. to o Airborne from 6.84(-2) take for the containment sample rate = 2.0 (-1)

, count

, o Containment

direct shine

!- = 5.0 (-3) l l 1 min to o Filter Cartridge 1.09 (-1)

place and No. 2 remove the (at 1 ft)

sample in = 6.54 the detector

! o Filter Cartridge 1.09 (-2)

~

No. 3 (at 2 ft.)

= 6.54 (-1) -

E 2.3.5 Radioactive Exposure to the Personnel During Post Accident MAP-5 Filter Removal Activities i All the action and motions by the personnel during the E post accident MAP-5 (at RMA-5) filter removal activities E are accounted for. The exposure for both whole body and i extremities due to each source are presented in i Table 11. Note that it is assumed that the technician E carries the MAP-5 filter cartridges in a bag one foot j away from his body.

The integrated whole body and extremity doses during the k post accident MAP-5 filter removal at RMA-5 are 1.1 rem

) and 6.0 rem respectively.

k 2.4 Radioactive Ex>osure to the Personnel During Post Accident MAP-5 l (er RMA-8 and (MA-9) Filter Removal Activities The MAP-5 fo: RMA-8 and RMA-9 are used for sampling Reactor Building Purge and Auxiliary ard Fuel Handling Building

. exhaust. The function of MAP-! at RMA-8 and RMA-9 is the same as MAP-5 at RMA-5. Since the source term for all MAP-5 is based on NUREG-0737 source term recomednation, the radioactive exposure to the personnel 'or MAP-5 filter removal at RMA-8 and

, RMA-9 is apsroximately the same as for MAP-5 at RMA-5 filter i

removal tasc.

, e TM 543 Fage 23 of 26 TABLE 11 RAD EXPOSUfT FOR KAP-5 FITTER RfM0 VAL ACTIVITIES _

Red Erposure Radiation level During Work Deserlotion_

Rayfire Radiation Source freet/ hr) (rtg)

Transit froe lab 2 min . Airborne from containment 2.0 (-1) 6.8 (-3) to MAP-5 panel . Contairveent direct shine 5.0 (-3) (W.B.)

Preperstion and 4 min . Airborne from containment 2.0 (-1) rnas 'ai of the & 30 ove . Conteirment direct shine 5.0 (-3) filters . Panel piping (et I ft.) 6.41 (-2) 5.6 (-1)

. Carteldge No. 2 (at 1 ft.) 6.54 (+0) (W.8.)

. Cartridge No. 3 (at 1 ft.) 6.54 (-1) 6.0(+0)

. Cartridge No. 2 (contact, 30 sec.) 6.59 (+2) (Entremity)

. Cartridge No. 3 (contact, 30 sec.) 6.59(+1)

Additional Time 6 min . Airborne from containment 2.0 (-1) in general aree . Containment direct shine 5.0 (-3) 5.8 (-2)

. Panel piping (at 5 ft.) 3.52 (-3) (W.8.)

. Cartridge No. 2 (at 5 ft.) 3.37 (-1)

. Cartridge No. 3 (at 5 ft.) 3.37 (-2)

Trencit from 2 min . Airborne from containment 2.0 (-1)

MA'-5 to lab & 15 eec . Containment direct shine 5.0 (-3) 2.8(-1)

. Cartridge No. 2 (at 1 ft.) 6.54 (+C) (W.B.)

. Cartridge No. 3 (at i ft.) 6.54 (-1)

Sarple Analysis 20 min. . See Section 2.3.4 1.9 (-1)

(W.B.)

Total Dose for the Teek (rea) 1.1 W.B.

6.0 Erttemity i

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Page 24 of 26

{ 2.5 Exposure Rate Common for RMA-5 Grab Sampling and MAP-5 Filter Removal Activities 5

E

! 2.5.1 Dose Rate Due to the Airborne From the Containment i

According to reference 5, the maximum ex- posure due to the airborne activity in the vicinity of the containment is 200 mrem /hr. This was based on Atmos- pheric Dilution Factor (X/Q) of 3.44 x 10~3 sec/m3 with wind speed of 0.782 m/sec and Pasquill Type of "F" condition.

Technicians are expected to follow plant procedure for

[ protective respirator requirements (RCP-1613) to reduce inhalation doses during the sampling.

2.5.2 Dose Rate Due to the Containment Direct Shine Radiation dose rate of 5 mrem /hr due to the containment shine used'in this report was taken from reference 6.

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-l 3.0 SulEARY OF RESULTS I

The radiation exposure to the technicians during post accident F conditions for RM-5 grab sampling and MAP-5 filter removal are:

F Whole Body Extremity .

(rem) (rem) i[ -NUREG-0737 5 75 Limits

. using marinneli beaker

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RNA-5 grab to carry the sample 1.3 (-1) 9.9 (-2)

sampling . using 25 cc bulb to l;

carry the sample 9.3 (-2) 8.5 (-3)

MAP-5 filter removal 1.1 (to) 6.0 (+0)

These values are in compliance with the limits set by NUREG-0737.

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4.0 REFERENCES

h 4 BNWL-236, UC-34 " User's Manual for ISOSHLD Code," June, 1966

{ l.

2. " Clarification of TMI Action Plan Requirements," Office of j Nuclear Reactor Regulation,NDivision of Licensing, U.S. Nuclear l

1

) Regulatory Comission (NUREG-0737) s

3. TMI-1 Operating Procedure 1004.31, Rev. S " Airborne Radioactivity Sampling and Analysis," 1/16/84 f 4. Conversation with Pat Connachie (Plant Radiological Engineering)

5. GPU Calculation No. A120-5412-016 "TMI-1; Post LOCA Airborne and

. Direct Shine Dose," 2/1/83

6. TDR No. 529 "TMI-1; Post Accident Containment Sanrpiing Radiological Analysis," 6/4/84, Rev. 0 l

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